ML20080D121
| ML20080D121 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/24/1983 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20080D115 | List: |
| References | |
| NUDOCS 8308300076 | |
| Download: ML20080D121 (5) | |
Text
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I EKCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION REVISIONS BROWNS FERRY NUCLEAR PLANT UNITS 1 AND 2 (TVA BFNP TS 176 SUPPLEMENT 10) l l
8308300076 830824 DR ADOCK 05000259 PDR
9 UNIT 1 Lp1ITIt:G CONDITIONS FOR OPZRATION SURVEILLANCE REQUIR2MENTS
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- 3. 7
[OffrAINMENT SYSTEMS 4.7 CONTAINMENT SYSTEMS c.
System ficw rate c.
Halogsnated shall be shown to be within hydrocarton
+ 10 % design f low testing shall be when tested in performed af ter each complete or accordance with partial ANSI N510-1975.
replacement of 3.
From and after the the charcoal date that one of the adsorter tank or l
control room after any structural emergency pressurization maintenance on systems is made or the system found to be housing.
inoparatte for any d.
Each circuit reason, reactor shall he ope ra tion or refueling operations opera ted a t is permissible only least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> during the succeeding every month.
7 days unless such circuit is sooner 3.
At least once per made operable.
operating cycle not to exceed 19. months,
(
s, 4
If these conditions automatic initiation cannot te met, of the control roca reactor shutdcwn emergency shall te initiated pressurization system l
and all reactors shall be shall be in cold demonstrated.
shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for reactor 4.
During the simulated operations and automatic actuation refueling operations test of this system shall be terminated (see Table
- 4. 2. G), it within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
shall be verified that the following dampers operate as indicated:
Close:
FcO-150 a,
D, E,
and F Open:
FCO-151 FCO-152 a
245 m,,.m-
..m m ea ses
- ~ =
- - *. - - = * ~ ~ * - - ~ - = ~ '
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UNIT 2 l-SURVEILLANCE RFOU I P2:ENTS LI::ITIt:G CONDITIO!!S FO? OPZRATION It.
V ytJtfr A! M2G,5 Y ST:C4:.
4.7 CONTAINMENT SYSTYMS c.
System f icw rate c.
H alog a:na ted shall be shown hydrocarbon to be within testing shall be 210% design flow performed after when tested in each complete or accordance with partial ANSI N510-1975.
replacement of the cha rcoal 3.
From and after the adsortar tank or j
date that one of the after any con t rol room structural emercency maintenanco on pressuri:ation the systen systems is made or housing.
fcund to te inoparatie for any d.
Each circuit reason, reactor shall t?
operation or operated at refueling operations least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> is permissible only every month.
during the succeeding 7 days unless such 3.
At least once per circuit is sooner operating cycle not made operable.
to exceed 19 months, automatic initiation s,,,
4 If the no conditions of the control rOO7 cannot te mat.
energency reactor nhuticvn prassurization system shall te initiated shall be and all reactor 3 demonstrated.
shall be in cold shutdoun within 24 4
During the si.-ulated hours for reactor autcmatic actuation operations and test of this sy7 tem refueling operations (see Table u. 2. G), it shall be terminated shall be verified within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
that the following dampers cperate as indicated:
Close:
FCO-150 B,
D, E, and F Cpen:
FCO-151 FCO-152
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245 e
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ENCLOSURE 2 DESCRIPTION OF PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS FOR BROWNS FERRY NUCLEAR PLANT UNITS 1 AND 2 (TS 176 SUPPLEMENT 10)
Page 245 - Technical specification 4.7.E.4 is being modified to delete FCOs 31-150A and 31-150C from the surveillance requirement. These isolatir: dampers were removed from the design of the ventilation system by ECN L-1242. The associated duct openings were closed so that no isolation function is now required.
This requested change to the technical specifications is needed to close out a concern of the Browns Ferry NRC resident inspector. The resident inspector discovered that FCOs 31-150A and 31-150C were not included in t
the associated surveillance instruction. Review revealed that they had been removed, but that a change to the technical specifications had not been made.
This proposed change will have no effect on the safety of plant operation, j
ENCLOSURE 3 BROWNS FERRY NUCLEAR PLANT SIGNIFICANT HAZARDS CONSIDERATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGES (TS 176 SUPPLEMENT 10) 1.
Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
No.
The change is administrat.ive in nature since it only removes isolation dampers FC0 31-150A and FC0 31-150C from the surveillance requirement. These dampers were removed from the design of the ventilation system-by ECN L-1242.
The associated duct openings were closed so that no isolation function is now required.
2.
Does the proposed amendment create the proability of a new or different kind of accident from any accident previously evaluated?
No.
See explanation in item 1.
3 Does the proposed amendment involve a significant reduction in a margin of safety?
No.
See explanation in item 1.
A~~
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